... Historically, the procedure for butt fusion joining of polyethylene pipe has been qualified on the basis of two fundamental tests that are widely recognized within the industry. These are the tensile-impact (T-I) test method found in ASTM F2634-07 and the reverse-bend (RB) or bend-back test...

... this case study relate to the importance of drilling fluid accuracy in the model. horizontal directional drilling PVC pipe pull force fusion modeling Reprinted from JAI, Vol. 8, No. 3 doi:10.1520/JAI102859 Available online at www.astm.org/JAI Richard (Bo) Botteicher1 and Samuel T. Ariaratnam2...

... This paper describes the sampling and analysis of beryllium at the Joint European Torus (JET) fusion facility. The current policy requiring 100 % personal air sampling (PAS) and taking many surface contamination smears generates 40,000 samples per year. Sample processing, analysis...

... Vanadium alloys, especially V-Cr-Ti alloys, are candidates for first wall and blanket structures of fusion reactors. However, a major vulnerability of this class of alloys is the affinity for oxygen and other interstitial solutes. Oxygen, nitrogen, carbon, and hydrogen can severely harden...

... In the late 1950s and early 1960s, inadequate fusion of PVC materials was a relatively frequent occurrence for North American PVC pipe manufacturers. As a result, an acetone-immersion test method was developed and published in 1963 as ASTM D2152 “Standard Test Method for Adequacy of Fusion...

... Tensile testing on three model Fe-Cr-Ni alloys removed from four discharges of the 59 Ni isotopic doping experiment in FFTF-MOTA indicates that helium/dpa ratios typical of fusion reactors do not produce changes in the yield strength or elongation that are significantly different from those...

.... The helium to dpa ratio and the transmutation product generation are calculated. These results are compared to expectations for the proposed DEMO fusion reactor and to FFTF. fusion irradiation facility LAMPF LASREF Monte Carlo Phillip D. Ferguson I, Gary E. Mueller I, Walter F. Sommer 2...

... surrounding the experiment and to safety factors in the computations. Fusion Tokamak Neutrons Thermoluminescence Activation Cobalt-58 Philippe Joyer1 and Gilles Martin 1 NEUTRON DOSIMETRY AND ACTIVATION ON THE TOKAMAK TORE-SUPRA REFERENCE: Joyer, P,, and Martin, G., "Neutron Dosimetry...

... A miniature-disk bending fatigue specimen was earlier developed for testing materials to be used for fusion reactor applications. The specimen is based on a 3-mm-diameter transmission electron microscope disk. A second larger rectangular specimen was also developed, with dimensions of 30.16...

... Currently envisioned fusion reactors require materials capable of operating in a high-energy irradiation environment and at elevated temperatures. In this study, two nonstandard miniature bending fatigue specimens have been developed for scoping candidate first wall materials for fusion reactors...

... will be less severe and the swelling less significant. fusion NET first wall austenitic stainless steel welds 316L 316LN European reference electron beam weld weld deposit OK 62 35 (19-12-2) irradiation tensile properties fracture mechanics fatigue crack growth rate low-cycle fatigue...

... of creep at 8 dpa are in good agreement with the results of the ORR-MFE-67/7J experiment. creep dislocation climb dislocation glide fusion irradiation creep point defects theoretical models transient effects Roger E. Stoller, ~Martin L. Grossbeck, ~a n d Louis K. M a n s u r I A Theoretical...

... of the microstructural evolution suggest that void nucleation is still progressing, and swelling could increase with dose. The effect of helium on void swelling remains a valid concern for fusion application that requires higher dose experiments. martensitic/ferritic steels helium nickel doping voids bubbles...

... Irradiation creep was investigated in the alloys—prime candidate alloy (PCA), Japanese Fusion Energy Program (JPCA), and American Iron and Steel Institute (AISI) 316 (UNS S31600) stainless steel. Tubes pressurized to stress levels of 50 to 400 MPa were irradiated in the Oak Ridge Research...

... Special austenitic steels are being designed in which alloying elements like molybdenum, niobium, and nickel are replaced with manganese, tungsten, vanadium, titanium, and/or tantalum to reduce the long-term radioactivity induced by fusion reactor irradiation. However, the new steels still need...

... European activities in the field of high energy neutron dosimetry as applied to fusion devices and spallation sources are outlined. The present status of the related neutron cross-section data is described, and the need for further work is considered. The survey concentrates on three topics: (1...

.... It is concluded that the spallation neutrons are accompanied by a few percent of high energy protons. dosimetry radiation damage spallation fusion activation detectors He-production cross sections A. Cesana, I R. Dierckx, 2 V. Sangiust, ~and M. Terrani ~ Dosimetry for a Radiation Damage Experiment...

... by dosimetry techniques, involving reaction rate measurements. The relevance of these exposure parameters with respect to experimental results was the topic of the workshop under discussion. neutrons fission fusion damage fluence irradiation effects A. Alberman 1and R. Dierckx 2 European...

... This paper describes a rapid, simple technique for solubilizing a wide range of materials such as ores, sinters, slags, ferro-alloys, and other reagents and additives used in integrated steel making operations including environmental dusts and particulate matter. The procedure involves fusion...

... to the preparation of many types of samples. This report reviews a selection of the techniques themselves and the results obtained from the analysis of several types of samples. dissolution chemical attack fusion microwave pressure bomb ultrasonic oxidation ashing analytical spectroscopy sample...